US6863745B1 - Zirconium based alloy and method for making a component for a nuclear fuel assembly with same - Google Patents

Zirconium based alloy and method for making a component for a nuclear fuel assembly with same Download PDF

Info

Publication number
US6863745B1
US6863745B1 US10/089,270 US8927002A US6863745B1 US 6863745 B1 US6863745 B1 US 6863745B1 US 8927002 A US8927002 A US 8927002A US 6863745 B1 US6863745 B1 US 6863745B1
Authority
US
United States
Prior art keywords
ppm
less
weight
zirconium
iron
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime, expires
Application number
US10/089,270
Inventor
Daniel Charquet
Jean Paul Mardon
Jean Senevat
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Compagnie Europeenne du Zirconium Cezus SA
Areva NP SAS
Original Assignee
Compagnie Europeenne du Zirconium Cezus SA
Framatome ANP SAS
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Compagnie Europeenne du Zirconium Cezus SA, Framatome ANP SAS filed Critical Compagnie Europeenne du Zirconium Cezus SA
Assigned to FRAMATOME ANP, COMPAGNIE EUROPEENNE DU ZIRCONIUM CEZUS reassignment FRAMATOME ANP ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: CHARQUET, DANIEL, MARDON, JEAN-PAUL, SENEVAT, JEAN
Application granted granted Critical
Publication of US6863745B1 publication Critical patent/US6863745B1/en
Adjusted expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Images

Classifications

    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C16/00—Alloys based on zirconium
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
    • C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
    • C22F1/16—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon
    • C22F1/18—High-melting or refractory metals or alloys based thereon
    • C22F1/186—High-melting or refractory metals or alloys based thereon of zirconium or alloys based thereon
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to zirconium-based alloys that are to constitute nuclear fuel assembly components usable in light-water nuclear reactors, such as nuclear fuel rod claddings or assembly guide tubes, or even flat products, such as grid plates.
  • the invention may be used, although not exclusively, in the field of the manufacture of cladding tubes for fuel rods intended for pressurized-water reactors in which the risks of corrosion are particularly high, and also in the field of strip materials used for structural components of the fuel assemblies of such reactors.
  • the invention also proposes a method for making such components.
  • Patent application PCT WO 99/50 854 proposes a zirconium-based alloy also containing, by weight, apart from unavoidable impurities, from 0.03 to 0.25% in total of iron, on the one hand, and of at least one of the elements of the group constituted by chromium and vanadium, on the other hand, having from 0.8 to 1.3% of niobium, less than 2000 ppm of tin, from 500 to 2000 ppm of oxygen, less than 100 ppm of carbon, from 5 to 35 ppm of sulphur and less than 50 ppm of silicon, the ratio of the iron content, on the one hand, to the chromium or vanadium content, on the other hand, being from 0.5 to 30.
  • the invention is based on observations made by the inventors in the course of a systematic study of the intermetallic phases and the crystallographic forms of those phases which appear when the relative contents of iron and niobium are varied while the contents of tin, sulphur and oxygen are described in the application mentioned above. It is also based on the observation, made experimentally, that the nature and the crystallographic form of the intermetallic phases containing zirconium, iron and niobium have a major influence on corrosion resistance in various environments.
  • the present invention aims especially to provide an alloy which enables components to be obtained wherein the composition may be adapted in an optimum manner to the conditions of use provided for and whose composition is not likely to hamper the manufacturing steps excessively.
  • the invention proposes, in particular, a zirconium-based alloy also containing, by weight, apart from unavoidable impurities, from 0.02 to 1% of iron having from 0.8% to 2.3% of niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 100 ppm of carbon, from 5 to 35 ppm of sulphur and from 0.01% to 0.25% in total of chromium and/or vanadium, the ratio R of the niobium content, less 0.5%, to the iron content, optionally supplemented by the chromium and/or vanadium content, being higher than 2.5. A ratio exceeding 3 may be used. In order to have a particularly high resistance to uniform corrosion, iron content may not exceed 0.35% as an example.
  • the oxygen content may be controlled in such a manner that it is from 1000 to 1600 ppm.
  • the invention also proposes a method for making a tube according to which:
  • the final thermal treatment leaves the tube in the recrystallized state, which promotes creep strength, without modifying the nature of the phases.
  • the ⁇ Nb phase precipitates and the hexagonal-lattice intermetallic compound of the type Zr (Nb, Fe, Cr, V) 2 co-exist.
  • the alloy may also be used to produce flat elements. Those elements are also used in the recrystallized state and can be manufactured by the following sequence: a blank is produced from a zirconium-based alloy also containing, by weight, in addition to unavoidable impurities, from 0.02 to 1% of iron, from 0.8% to 2.3% of niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 100 ppm of carbon, from 5 to 35 ppm of sulphur and less than 0.25% in total of chromium and/or vanadium, the ratio of the niobium content less 0.5% to the iron content, optionally supplemented by the chromium and/or vanadium content, being higher than 2.5,
  • the invention also proposes the application of the above alloy to the production of components of nuclear reactors operating with pressurized water that contains less than 3.5 ppm of lithium.
  • an alloy of the above type having a use in the recrystallized state to increase its resistance to the bi-axial creep of tubes and the aptitude for the pressing of sheet metal has characteristics which are adjustable by regulating the iron/niobium ratio but which are still favorable; in particular, it has a high corrosion resistance in an aqueous medium at high temperature, the resistance being all the higher if a high iron content is adopted, this being permitted by a high Nb content.
  • the ranges given below are particularly valuable as a zirconium-based alloy also containing, by weight, apart from unavoidable impurities: from 1 to 1.8% by weight of niobium, from 0.1 to 0.3% by weight of iron, from 0.15 to 0.20% by weight of tin, from 0.01 to 0.1% by weight of chromium and/or vanadium, from 1000 to 1600 ppm of oxygen, less than 100 ppm of carbon and from 5 to 35 ppm of sulphur.
  • FIG. 1 is a ternary diagram showing the intermetallic compounds and microstructures which appear for various ranges of composition, in the case of a content of 0.2% of tin, at a temperature of from 560° C. to 620° C.
  • FIG. 2 illustrates a fraction of the diagram on a large scale.
  • the C, Si and O 2 contents of obtained samples are substantially identical for all of the samples and were lower than the maximum values given above.
  • the tin content was 0.2% and the sulphur content was 10 ppm.
  • the samples were manufactured by thermo-metallurgical operations at a temperature not exceeding 620° C., any treatment exceeding that value beyond the extrusion operation reducing corrosion resistance at high temperature.
  • the ternary diagram in FIG. 1 shows, for Fe/Nb ratios lower than approximately 0.3, the existence of a region in which the aZr phase (with the exclusion of the bZr phase which is very detrimental from the point of view of corrosion resistance), the bNb phase precipitates and the intermetallic phase Zr (Nb, Fe) 2 , which has a hexagonal structure, co-exist.
  • the compounds corresponding to a ratio (Nb—0.5%)/Fe+Cr+V higher than a threshold which is always higher than 2.5, as an example, are used when the main phenomenon to be combated is uniform corrosion in high-temperature water having a low lithium content.
  • the hexagonal Zr (Nb, Fe) 2 form appears which substitutes the bNb phase for a ratio by weight of Nb/Fe substantially equal to 2.3.
  • the diagram illustrates that, by simultaneously increasing the content of Nb and of Fe, a higher density of intermetallics is obtained, which promotes corrosion in an aqueous medium.
  • the following table shows the influence of the increasing iron content, which does not impair uniform corrosion for an alloy with 1% niobium, the other elements having contents such as described above.

Abstract

The invention proposes a zirconium-based alloy also containing, by weight, apart from unavoidable impurities, from 0.02 to 1% of iron having from 0.8% to 2.3% of niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 100 ppm of carbon, from 5 to 35 ppm of sulphur and from 0.01% to 0.25% in total of chromium and/or vanadium, the ratio R of the niobium content, less 0.5%, to the iron content, optionally supplemented by the chromium and/or vanadium content.

Description

FIELD OF THE INVENTION
The present invention relates to zirconium-based alloys that are to constitute nuclear fuel assembly components usable in light-water nuclear reactors, such as nuclear fuel rod claddings or assembly guide tubes, or even flat products, such as grid plates.
The invention may be used, although not exclusively, in the field of the manufacture of cladding tubes for fuel rods intended for pressurized-water reactors in which the risks of corrosion are particularly high, and also in the field of strip materials used for structural components of the fuel assemblies of such reactors. The invention also proposes a method for making such components.
BACKGROUND INFORMATION
Patent application PCT WO 99/50 854 proposes a zirconium-based alloy also containing, by weight, apart from unavoidable impurities, from 0.03 to 0.25% in total of iron, on the one hand, and of at least one of the elements of the group constituted by chromium and vanadium, on the other hand, having from 0.8 to 1.3% of niobium, less than 2000 ppm of tin, from 500 to 2000 ppm of oxygen, less than 100 ppm of carbon, from 5 to 35 ppm of sulphur and less than 50 ppm of silicon, the ratio of the iron content, on the one hand, to the chromium or vanadium content, on the other hand, being from 0.5 to 30.
The invention is based on observations made by the inventors in the course of a systematic study of the intermetallic phases and the crystallographic forms of those phases which appear when the relative contents of iron and niobium are varied while the contents of tin, sulphur and oxygen are described in the application mentioned above. It is also based on the observation, made experimentally, that the nature and the crystallographic form of the intermetallic phases containing zirconium, iron and niobium have a major influence on corrosion resistance in various environments.
In particular, it has been found that the presence of compounds Zr (Nb, Fe)2 having a crystalline structure with a hexagonal lattice, and of the phase βNb substantially improves corrosion in the aqueous medium which exists in the majority of pressurized-water reactors.
SUMMARY
The present invention aims especially to provide an alloy which enables components to be obtained wherein the composition may be adapted in an optimum manner to the conditions of use provided for and whose composition is not likely to hamper the manufacturing steps excessively.
To that end, the invention proposes, in particular, a zirconium-based alloy also containing, by weight, apart from unavoidable impurities, from 0.02 to 1% of iron having from 0.8% to 2.3% of niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 100 ppm of carbon, from 5 to 35 ppm of sulphur and from 0.01% to 0.25% in total of chromium and/or vanadium, the ratio R of the niobium content, less 0.5%, to the iron content, optionally supplemented by the chromium and/or vanadium content, being higher than 2.5. A ratio exceeding 3 may be used. In order to have a particularly high resistance to uniform corrosion, iron content may not exceed 0.35% as an example.
The choice of the ratio R results from the observation that the phase having a hexagonal lattice does not appear until the relation between the content of Fe (and also of Cr and V if they are present) and the content of Nb is such that R exceeds a threshold which depends slightly on the contents of other elements and on the temperature, but is still higher than 2.5.
The oxygen content may be controlled in such a manner that it is from 1000 to 1600 ppm.
The invention also proposes a method for making a tube according to which:
    • a bar is produced from a zirconium-based alloy also containing, by weight, apart from unavoidable impurities, from 0.02 to 1% of iron, from 0.8% to 2.3% of niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 100 ppm of carbon, from 5 to 35 ppm of sulphur and from 0.01% to 0.25% in total of chromium and/or vanadium, the ratio of the niobium content less 0.5% to the iron content, optionally supplemented by the chromium and/or vanadium content, being higher than 2.5;
    • the bar is water-quenched after heating at from 1000° C. to 1200° C.;
    • a blank is extruded after heating at a temperature of from 600° C. to 800° C.;
    • the blank is cold-rolled in at least two passes to obtain a tube, with intermediate thermal treatments at from 560° C. to 620° C.; and
    • a final thermal treatment is carried out at from 560° C. to 620° C., all of the thermal treatments being carried out in an inert atmosphere or under vacuum.
The final thermal treatment leaves the tube in the recrystallized state, which promotes creep strength, without modifying the nature of the phases.
With the method described above, the βNb phase precipitates and the hexagonal-lattice intermetallic compound of the type Zr (Nb, Fe, Cr, V)2 co-exist.
The alloy may also be used to produce flat elements. Those elements are also used in the recrystallized state and can be manufactured by the following sequence: a blank is produced from a zirconium-based alloy also containing, by weight, in addition to unavoidable impurities, from 0.02 to 1% of iron, from 0.8% to 2.3% of niobium, less than 2000 ppm of tin, less than 2000 ppm of oxygen, less than 100 ppm of carbon, from 5 to 35 ppm of sulphur and less than 0.25% in total of chromium and/or vanadium, the ratio of the niobium content less 0.5% to the iron content, optionally supplemented by the chromium and/or vanadium content, being higher than 2.5,
    • the blank is cold-rolled in at least three passes, with intermediate thermal treatments and a final thermal treatment,
    • one of those intermediate thermal treatments or a preliminary thermal treatment before the first cold-rolling pass being effected for a long period of at least 2 hours at a temperature lower than 600° C., and
    • any thermal treatment following the long treatment and, in particular, the final recrystallization treatment, being effected at a temperature lower than 620° C.
The invention also proposes the application of the above alloy to the production of components of nuclear reactors operating with pressurized water that contains less than 3.5 ppm of lithium.
The existence of the intermetallic compounds, which is due to the presence of iron in a sufficient quantity, and particularly the existence of Zr (Nb, Fe)2, reduces the amount of niobium precipitates in phase β, but also the niobium content of the solid solution and gives good resistance to uniform corrosion at a temperature of 400° C., which is representative of the temperature that prevails in reactors. For a Fe/Nb ratio lower than 0.25, the βNb phase is hardly present.
The presence of chromium and/or vanadium as a very partial replacement for iron and/or niobium in the intermetallic precipitates of the type Zr (Nb, Fe, Cr, V)2 has no marked effect on corrosion at 400° C. The improved corrosion resistance at 400° C. is maintained especially if the sum Fe+Cr is at least 0.03%.
To summarize, an alloy of the above type having a use in the recrystallized state to increase its resistance to the bi-axial creep of tubes and the aptitude for the pressing of sheet metal has characteristics which are adjustable by regulating the iron/niobium ratio but which are still favorable; in particular, it has a high corrosion resistance in an aqueous medium at high temperature, the resistance being all the higher if a high iron content is adopted, this being permitted by a high Nb content.
It also has a high creep strength owing to the presence of tin which remains at a very low content and, owing to doping with oxygen, at a content lower than 2000 ppm, which then has no harmful effect on corrosion resistance.
In current reactors, the ranges given below are particularly valuable as a zirconium-based alloy also containing, by weight, apart from unavoidable impurities: from 1 to 1.8% by weight of niobium, from 0.1 to 0.3% by weight of iron, from 0.15 to 0.20% by weight of tin, from 0.01 to 0.1% by weight of chromium and/or vanadium, from 1000 to 1600 ppm of oxygen, less than 100 ppm of carbon and from 5 to 35 ppm of sulphur.
BRIEF DESCRIPTION OF THE DRAWINGS
The above characteristics and others will emerge more clearly on reading the following description of particular embodiments which are given by way of non-limiting example. The description refers to the drawings which accompany it and in which:
FIG. 1 is a ternary diagram showing the intermetallic compounds and microstructures which appear for various ranges of composition, in the case of a content of 0.2% of tin, at a temperature of from 560° C. to 620° C.
FIG. 2 illustrates a fraction of the diagram on a large scale.
 DETAILED DESCRIPTION
Referring to the figures, the C, Si and O2 contents of obtained samples are substantially identical for all of the samples and were lower than the maximum values given above. The tin content was 0.2% and the sulphur content was 10 ppm.
The samples were manufactured by thermo-metallurgical operations at a temperature not exceeding 620° C., any treatment exceeding that value beyond the extrusion operation reducing corrosion resistance at high temperature.
The ternary diagram in FIG. 1 shows, for Fe/Nb ratios lower than approximately 0.3, the existence of a region in which the aZr phase (with the exclusion of the bZr phase which is very detrimental from the point of view of corrosion resistance), the bNb phase precipitates and the intermetallic phase Zr (Nb, Fe)2, which has a hexagonal structure, co-exist.
The compounds, corresponding to a ratio (Nb—0.5%)/Fe+Cr+V higher than a threshold which is always higher than 2.5, as an example, are used when the main phenomenon to be combated is uniform corrosion in high-temperature water having a low lithium content.
For a high Fe/Nb ratio, up to a niobium content of the order of 50%, which is higher by more than one order of magnitude than the contents used, the compound (Zr, Nb)4Fe2, which is face-centered cubic, also appears.
When the conditions of use make it desirable to have intermetallic compounds that have only or predominantly a hexagonal structure, it is found that the result is achieved by adopting a Fe/Nb ratio lower than 0.3, while also respecting the relation (Nb—0.5%)/Fe+Cr+V>2.5.
A precise study of the diagram for the low Fe and Nb contents shows that the Nb content in solid solution develops with the Fe content, with Nb remaining constant.
As soon as the Fe content exceeds 60-70 ppm for the alloy according to the present invention, the hexagonal Zr (Nb, Fe)2 form appears which substitutes the bNb phase for a ratio by weight of Nb/Fe substantially equal to 2.3.
There then appears the face-centered cubic compound (Zr, Nb)4Fe2, corresponding to a Nb/Fe ratio substantially equal to 0.6.
This cubic phase (Zr, Nb)4Fe2 starts to appear for:
    • 1% Nb from 0.29 to 0.44% Fe
    • 1.5% Nb from 0.49 to 0.66% Fe
    • 2% Nb beyond 0.78% Fe.
The diagram illustrates that, by simultaneously increasing the content of Nb and of Fe, a higher density of intermetallics is obtained, which promotes corrosion in an aqueous medium.
The following table shows the influence of the increasing iron content, which does not impair uniform corrosion for an alloy with 1% niobium, the other elements having contents such as described above.
Increase in weight in mg/dm2
415° C. vapour, 311 days,
Fe % by weight 105 bar
0.03 490
0.15 456
0.29 455

Claims (9)

1. A zirconium based alloy comprising:
zirconium; and
in addition to unavoidable impurities, by weight, from 0.02 to 1% iron; from 0.8% to 2.3% niobium, less than 2000 ppm tin, less than 2000 ppm oxygen, less than 100 ppm carbon, from 5 to 35 ppm sulfur and from 0.01% to 0.25% in total of at least one of chromium and vanadium, a ratio (Nb—0.5%)/(Fe+Cr+V) being higher than 2.5.
2. The alloy according to claim 1, wherein the oxygen is from 1000 to 1600 ppm.
3. The alloy according to claim 1, wherein the niobium is from 1 to 1.8% by weight, the iron is from 0.1 to 0.3% by weight, the tin is from 0.15 to 0.20% by weight, the at least one of chromium and vanadium is from 0.01 to 0.1% by weight, the oxygen is from 1000 to 1600 ppm, the carbon is less than 100 ppm and the sulfur is from 5 to 35 ppm.
4. A tube comprising:
a tubular arranged zirconium-based alloy wherein the alloy comprises:
zirconium; and
in addition to unavoidable impurities, by weight, from 0.02 to 1% iron; from 0.8 to 2.3% niobium, less than 2000 ppm tin, less than 2000 ppm oxygen, less than 100 ppm carbon, from 5 to 35 ppm sulfur and from 0.01% to 0.25% in total of at least one of chromium and vanadium, a ratio of (Nb—0.5%)/(Fe+Cr+V) being higher than 2.5 in a recrystallized state.
5. A flat product comprising:
a flat arranged zirconium based alloy wherein the alloy comprises:
zirconium; and
in addition to unavoidable impurities, by weight, from 0.02 to 1% iron; from 0.8% to 2.3% niobium, less than 2000 ppm tin, less than 2000 ppm oxygen, less than 100 ppm carbon, from 5 to 35 ppm sulfur and from 0.01% to 0.25% in total of at least one of chromium and vanadium, a ratio (Nb—0.5%)/(Fe+Cr+V) being higher than 2.5 in a recrystallized state.
6. A method of using a component comprising:
providing the component made of an alloy comprising:
zirconium; and
in addition to unavoidable impurities, by weight, from 0.02 to 1% iron; from 0.8% to 2.3% niobium, less than 2000 ppm tin, less than 2000 ppm oxygen, less than 100 ppm carbon, from 5 to 35 ppm sulfur and from 0.01% to 0.25% in total of at least one of chromium and vanadium, a ratio of (Nb—0.5%)/(Fe+Cr+V) being higher than 2.5 in a recrystallized state; and
utilizing the component in a pressurized water reactor, wherein water initially contains less than 3.5 ppm of lithium.
7. The alloy according to claim 1, wherein the ratio is higher than 3.
8. The alloy according to claim 1, wherein the iron content does not exceed 0.35%.
9. A method for making a tube to constitute at least one of all and an external portion of at least one of nuclear fuel rod cladding and a guide tube for a nuclear fuel assembly comprising:
producing a bar from a zirconium-based alloy also containing by weight apart from unavoidable impurities, by weight, from 0.02 to 1% iron; from 0.8% to 2.3% niobium, less than 2000 ppm tin, less than 2000 ppm oxygen, less than 100 ppm carbon, from 5 to 35 ppm sulfur and from 0.01% to 0.25% in total of at least one of chromium and vanadium, a ratio (Nb—0.5%)/(Fe+Cr+V) being higher than 2.5;
water-quenching the bar after heating at from 1000° C. to 1200° C.;
extruding a blank after heating at from 600° C. to 800° C.;
cold rolling the blank in at least two passes to obtain a tube, with intermediate thermal treatments at from 560 C to 620 C; and
carrying out a final thermal treatment at from 560 C to 620 C, all of the thermal treatments being carried out in at least one of an inert atmosphere and under vacuum.
US10/089,270 1999-09-30 2000-09-28 Zirconium based alloy and method for making a component for a nuclear fuel assembly with same Expired - Lifetime US6863745B1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR9912248A FR2799210B1 (en) 1999-09-30 1999-09-30 ZIRCONIUM-BASED ALLOY AND METHOD OF MANUFACTURING COMPONENT FOR ASSEMBLY OF NUCLEAR FUEL IN SUCH AN ALLOY
PCT/FR2000/002680 WO2001024194A1 (en) 1999-09-30 2000-09-28 Zirconium-based alloy and method for making a component for a nuclear fuel assembly with same

Publications (1)

Publication Number Publication Date
US6863745B1 true US6863745B1 (en) 2005-03-08

Family

ID=9550459

Family Applications (1)

Application Number Title Priority Date Filing Date
US10/089,270 Expired - Lifetime US6863745B1 (en) 1999-09-30 2000-09-28 Zirconium based alloy and method for making a component for a nuclear fuel assembly with same

Country Status (12)

Country Link
US (1) US6863745B1 (en)
EP (1) EP1216480B1 (en)
JP (1) JP4644405B2 (en)
KR (1) KR100723818B1 (en)
CN (1) CN1150562C (en)
DE (1) DE60024113T2 (en)
ES (1) ES2248128T3 (en)
FR (1) FR2799210B1 (en)
RU (1) RU2261487C2 (en)
TW (1) TW522409B (en)
WO (1) WO2001024194A1 (en)
ZA (1) ZA200202516B (en)

Cited By (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20040118491A1 (en) * 1998-03-31 2004-06-24 Jean-Paul Mardon Alloy and tube for nuclear fuel assembly and method for making same
US20050061408A1 (en) * 1999-09-30 2005-03-24 Daniel Charquet Zirconium-based alloy and method for making a component for nuclear fuel assembly with same
US20100108204A1 (en) * 2008-05-09 2010-05-06 Korea Atomic Energy Research Institute Zirconium alloy composition for nuclear fuel cladding tube forming protective oxide film, zirconium alloy nuclear fuel cladding tube manufactured using the composition, and method of manufacturing the zirconium alloy nuclear fuel cladding tube
US20110158374A1 (en) * 1998-03-31 2011-06-30 Jean-Paul Mardon Alloy and tube for nuclear fuel assembly and method for making same
US8116423B2 (en) 2007-12-26 2012-02-14 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
US8654917B2 (en) 2007-12-26 2014-02-18 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
US9284629B2 (en) 2004-03-23 2016-03-15 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance due to final heat treatments
US9355747B2 (en) 2008-12-25 2016-05-31 Thorium Power, Inc. Light-water reactor fuel assembly (alternatives), a light-water reactor, and a fuel element of fuel assembly
US10037823B2 (en) 2010-05-11 2018-07-31 Thorium Power, Inc. Fuel assembly
US10119181B2 (en) 2013-01-11 2018-11-06 Areva Np Treatment process for a zirconium alloy, zirconium alloy resulting from this process and parts of nuclear reactors made of this alloy
US10170207B2 (en) 2013-05-10 2019-01-01 Thorium Power, Inc. Fuel assembly
US10192644B2 (en) 2010-05-11 2019-01-29 Lightbridge Corporation Fuel assembly
US10221475B2 (en) 2004-03-23 2019-03-05 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2799209B1 (en) * 1999-09-30 2001-11-30 Framatome Sa ZIRCONIUM-BASED ALLOY AND METHOD OF MANUFACTURING COMPONENT FOR ASSEMBLY OF NUCLEAR FUEL IN SUCH AN ALLOY
KR100461017B1 (en) 2001-11-02 2004-12-09 한국수력원자력 주식회사 Method for preparing niobium-containing zirconium alloys for nuclear fuel cladding tubes having the excellent corrosion resistance
FR2874119B1 (en) * 2004-08-04 2006-11-03 Framatome Anp Sas METHOD FOR MANUFACTURING A FUEL SINK TUBE FOR A NUCLEAR REACTOR, AND A TUBE THUS OBTAINED
FR2890767B1 (en) * 2005-09-09 2007-10-19 Framatome Anp Sas METHOD FOR DETERMINING AT LEAST ONE FACTOR OF TECHNOLOGICAL UNCERTAINTY OF NUCLEAR FUEL ELEMENTS, DESIGN METHOD, MANUFACTURING METHOD AND METHOD FOR CONTROLLING CORRESPONDING NUCLEAR FUEL ELEMENTS
FR2909798A1 (en) * 2006-12-11 2008-06-13 Areva Np Sas Designing fuel assembly, useful for light-water nuclear reactor comprising structural components of zirconium alloy, comprises calculating uniaxial constraints using traction/compression and choosing the alloys
WO2012173738A1 (en) * 2011-06-16 2012-12-20 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance due to final heat treatments
CN105018795B (en) * 2015-07-31 2017-09-12 西部新锆核材料科技有限公司 A kind of nuclear reactor fuel can zirconium-base alloy of fine corrosion resistance

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1993016205A1 (en) 1992-02-14 1993-08-19 Combustion Engineering, Inc. Creep resistant zirconium alloy
WO1997005628A1 (en) 1995-07-27 1997-02-13 Framatome Tube for a nuclear fuel assembly and method for making same
US5832050A (en) * 1996-04-16 1998-11-03 Compagnie Europeene Du Zirconium Cezus Zirconium-based alloy, manufacturing process, and use in a nuclear reactor
FR2769637A1 (en) 1997-10-13 1999-04-16 Mitsubishi Materials Corp Zirconium alloy nuclear fuel cladding production
WO1999050854A1 (en) 1998-03-31 1999-10-07 Framatome Alloy and tube for nuclear fuel assembly and method for making same
US6544361B1 (en) * 1999-02-15 2003-04-08 Framatome Anp Process for manufacturing thin components made of zirconium-based alloy and straps thus produced

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2701986B2 (en) * 1993-07-28 1998-01-21 ウセロッシスキー・ナウクノ−イッスレッドオワテルスキー・インスティテュト・ネオルガニシェスキクー・マテリアロフ・イメニ・アカデミカ・アー・アー・ボックワラ Zirconium-based materials, products for use in nuclear reactor cores made therefrom, and methods of making such products
FR2799209B1 (en) * 1999-09-30 2001-11-30 Framatome Sa ZIRCONIUM-BASED ALLOY AND METHOD OF MANUFACTURING COMPONENT FOR ASSEMBLY OF NUCLEAR FUEL IN SUCH AN ALLOY

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1993016205A1 (en) 1992-02-14 1993-08-19 Combustion Engineering, Inc. Creep resistant zirconium alloy
WO1997005628A1 (en) 1995-07-27 1997-02-13 Framatome Tube for a nuclear fuel assembly and method for making same
US5832050A (en) * 1996-04-16 1998-11-03 Compagnie Europeene Du Zirconium Cezus Zirconium-based alloy, manufacturing process, and use in a nuclear reactor
FR2769637A1 (en) 1997-10-13 1999-04-16 Mitsubishi Materials Corp Zirconium alloy nuclear fuel cladding production
WO1999050854A1 (en) 1998-03-31 1999-10-07 Framatome Alloy and tube for nuclear fuel assembly and method for making same
US6544361B1 (en) * 1999-02-15 2003-04-08 Framatome Anp Process for manufacturing thin components made of zirconium-based alloy and straps thus produced

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
"ASM Handbook: vol. 2 Properties and Selection: Nonferrous Alloys and Special-Purpose Materials", ASM International, 1990, pp 662-663. *

Cited By (21)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7985373B2 (en) * 1998-03-31 2011-07-26 Framatome Anp Alloy and tube for nuclear fuel assembly and method for making same
US20040118491A1 (en) * 1998-03-31 2004-06-24 Jean-Paul Mardon Alloy and tube for nuclear fuel assembly and method for making same
US20110158374A1 (en) * 1998-03-31 2011-06-30 Jean-Paul Mardon Alloy and tube for nuclear fuel assembly and method for making same
US20050061408A1 (en) * 1999-09-30 2005-03-24 Daniel Charquet Zirconium-based alloy and method for making a component for nuclear fuel assembly with same
US7627075B2 (en) * 1999-09-30 2009-12-01 Framatome Anp Zirconium-based alloy and method for making a component for nuclear fuel assembly with same
US9725791B2 (en) 2004-03-23 2017-08-08 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance due to final heat treatments
US10221475B2 (en) 2004-03-23 2019-03-05 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance
US9284629B2 (en) 2004-03-23 2016-03-15 Westinghouse Electric Company Llc Zirconium alloys with improved corrosion/creep resistance due to final heat treatments
US8654917B2 (en) 2007-12-26 2014-02-18 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
US8116423B2 (en) 2007-12-26 2012-02-14 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
US20100108204A1 (en) * 2008-05-09 2010-05-06 Korea Atomic Energy Research Institute Zirconium alloy composition for nuclear fuel cladding tube forming protective oxide film, zirconium alloy nuclear fuel cladding tube manufactured using the composition, and method of manufacturing the zirconium alloy nuclear fuel cladding tube
US9355747B2 (en) 2008-12-25 2016-05-31 Thorium Power, Inc. Light-water reactor fuel assembly (alternatives), a light-water reactor, and a fuel element of fuel assembly
US10192644B2 (en) 2010-05-11 2019-01-29 Lightbridge Corporation Fuel assembly
US10037823B2 (en) 2010-05-11 2018-07-31 Thorium Power, Inc. Fuel assembly
US10991473B2 (en) 2010-05-11 2021-04-27 Thorium Power, Inc. Method of manufacturing a nuclear fuel assembly
US11195629B2 (en) 2010-05-11 2021-12-07 Thorium Power, Inc. Fuel assembly
US11837371B2 (en) 2010-05-11 2023-12-05 Thorium Power, Inc. Method of manufacturing a nuclear fuel assembly
US11862353B2 (en) 2010-05-11 2024-01-02 Thorium Power, Inc. Fuel assembly
US10119181B2 (en) 2013-01-11 2018-11-06 Areva Np Treatment process for a zirconium alloy, zirconium alloy resulting from this process and parts of nuclear reactors made of this alloy
US10170207B2 (en) 2013-05-10 2019-01-01 Thorium Power, Inc. Fuel assembly
US11211174B2 (en) 2013-05-10 2021-12-28 Thorium Power, Inc. Fuel assembly

Also Published As

Publication number Publication date
DE60024113T2 (en) 2006-04-13
CN1399780A (en) 2003-02-26
WO2001024194A1 (en) 2001-04-05
EP1216480B1 (en) 2005-11-16
TW522409B (en) 2003-03-01
RU2261487C2 (en) 2005-09-27
JP2003516470A (en) 2003-05-13
FR2799210A1 (en) 2001-04-06
DE60024113D1 (en) 2005-12-22
CN1150562C (en) 2004-05-19
KR20020057965A (en) 2002-07-12
ES2248128T3 (en) 2006-03-16
JP4644405B2 (en) 2011-03-02
ZA200202516B (en) 2003-07-30
EP1216480A1 (en) 2002-06-26
KR100723818B1 (en) 2007-06-04
FR2799210B1 (en) 2001-11-30

Similar Documents

Publication Publication Date Title
US6863745B1 (en) Zirconium based alloy and method for making a component for a nuclear fuel assembly with same
EP0415134B1 (en) Zirconium based alloy material for light water reactor applications
US6811746B2 (en) Zirconium alloy having excellent corrosion resistance and mechanical properties for nuclear fuel cladding tube
US20060243358A1 (en) Zirconium alloys with improved corrosion resistance and method for fabricating zirconium alloys with improved corrosion
US5832050A (en) Zirconium-based alloy, manufacturing process, and use in a nuclear reactor
US7364631B2 (en) Zirconium-based alloy having a high resistance to corrosion and to hydriding by water and steam and process for the thermomechanical transformation of the alloy
WO2013182177A1 (en) Nickel-chromium-aluminum alloy having good processability, creep resistance and corrosion resistance
US5017336A (en) Zironium alloy for use in pressurized nuclear reactor fuel components
RU2261486C2 (en) Zirconium base alloy and method for manufacturing nuclear-reactor fuel-assembly element from this alloy
US6544361B1 (en) Process for manufacturing thin components made of zirconium-based alloy and straps thus produced
KR101108935B1 (en) Method of producing a flat zirconium alloy porduct, flat product thus obtained and nuclear plant reactor grid which is made from said flat product
DE2534786C3 (en) Nickel-chromium-tungsten alloy and its uses
EP1627090B1 (en) Zirconium alloy and components for the core of light water cooled nuclear reactors
DE3703168C2 (en)
DE2422578A1 (en) ZIRCONALIZATION, PROCESS FOR THEIR MANUFACTURING AND THEIR USE
US7627075B2 (en) Zirconium-based alloy and method for making a component for nuclear fuel assembly with same
CA1145165A (en) Fe-based long range ordered alloys
DE102020132193A1 (en) Use of a nickel-chromium-iron-aluminum alloy with good workability, creep resistance and corrosion resistance
JP2687538B2 (en) Zr alloy for nuclear reactor fuel assemblies
US5122334A (en) Zirconium-gallium alloy and structural components made thereof for use in nuclear reactors
US20040118491A1 (en) Alloy and tube for nuclear fuel assembly and method for making same
US7985373B2 (en) Alloy and tube for nuclear fuel assembly and method for making same
DE3306540A1 (en) METHODS AND ALLOYS FOR THE PRODUCTION OF FORGED COMPONENTS FOR GAS-COOLED HIGH-TEMPERATURE REACTORS
DE1289992B (en) Use of titanium alloys for high-strength, corrosion-resistant objects that are exposed to atmospheres contaminated with fluorine

Legal Events

Date Code Title Description
AS Assignment

Owner name: FRAMATOME ANP, FRANCE

Free format text: ASSIGNMENT OF ASSIGNORS INTEREST;ASSIGNORS:CHARQUET, DANIEL;MARDON, JEAN-PAUL;SENEVAT, JEAN;REEL/FRAME:013037/0462

Effective date: 20020402

Owner name: COMPAGNIE EUROPEENNE DU ZIRCONIUM CEZUS, FRANCE

Free format text: ASSIGNMENT OF ASSIGNORS INTEREST;ASSIGNORS:CHARQUET, DANIEL;MARDON, JEAN-PAUL;SENEVAT, JEAN;REEL/FRAME:013037/0462

Effective date: 20020402

STCF Information on status: patent grant

Free format text: PATENTED CASE

FEPP Fee payment procedure

Free format text: PAYOR NUMBER ASSIGNED (ORIGINAL EVENT CODE: ASPN); ENTITY STATUS OF PATENT OWNER: LARGE ENTITY

FPAY Fee payment

Year of fee payment: 4

FPAY Fee payment

Year of fee payment: 8

FPAY Fee payment

Year of fee payment: 12